ORAUT-OTIB-0054, Finding 9 (Workbook) 1 SC&A – April 2, 2015 

NOTICE: This document has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

SC&A’s Evaluation of OTIB-0054 Workbook 1.5.11 

with Air Concentration Data 

Ron Buchanan, SC&A 

April 2, 2015 

Introduction 

SC&A evaluated the ORAUT-OTIB-0054 workbook in conjunction with the current version of 

ORAUT-OTIB-0054, Rev. 03, February 6, 2015 (Fission and Activation Product Assignment for 

Internal Dose-Related Gross Beta and Gross Gamma Analyses) (referred to as OTIB-0054). The 

sequence of the release of OTIB-0054 and its related Workbook is as follows: 

5/11/2007, Rev. 00 of OTIB-0054 (ORAUT 2007a) 

10/09/2007, Ver. 1.01 of OTIB-0054 Workbook (ORAUT 2007b) 

11/19/2007, Rev. 00 PC-1 of OTIB-0054 (ORAUT 2007c) 

6/13/2013, Rev. 01 of OTIB-0054 (ORAUT 2013a) 

11/21/2013, Ver. 1.2.0 of OTIB-0054 Workbook (ORAUT 2013b) 

3/06/2014, Rev. 02 of OTIB-0054. (ORAUT 2014) 

2/06/2015, Rev. 03 of OTIB-0054. (ORAUT 2015a) 

 March 2015, Ver. 1.5.11 of OTIB-0054 Workbook (ORAUT 2015b) 

SC&A evaluated OTIB-0054 Workbook 1.2.0 in April 2014 (SC&A 2014) and found that the 

workbook performed correctly when using urine bioassay data, but it did not perform correctly 

when using air concentration data. 

To evaluate OTIB-0054 Workbook 1.5.11 (referred to as the Workbook), SC&A analyzed the 

three examples provided on pages 68–71 of OTIB-0054 to verify the methodology and 

compatibility of the examples with the text and tables of OTIB-0054. SC&A then ran the intake 

calculations for these three examples using the OTIB-0054 Workbook 1.5.11. An example of 

the data input screen for the Workbook is shown in Exhibit A below. 
ORAUT-OTIB-0054, Finding 9 (Workbook) 2 SC&A – April 2, 2015 

NOTICE: This document has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

Exhibit A. Example of OTIB-0054 Workbook 1.5.11 Data Input Screen 

Operation of Workbook 1.5.11 

Inputs 

The input screen and operation of Workbook 1.5.11 is different than the older version of the 

Workbook (1.2.0) only in that it contains a button labeled “Apply Air Sample Activity Fraction.” 

The OTIB-0054 Workbook 1.5.11 is located in the DR Tools folder and can only be accessed 

through the use of the DR Tools unique password. To illustrate the use of the newer version, a 

summary of its inputs and operations will be provided: 

 As the copy of the screen above indicates, you are required to enter the exposure start 

year, the end year, and the year the cancer was diagnosed 

 Select if it is based on a Sr-90 beta or Cs-137 gamma as the indicator 

 Enter the intake value of the gross beta or gamma indicator (in any of the units provided) 

 Select the decay time 

 Select the reactor group type(s) 

 Select chronic or acute exposure 

 Select the amount of urine sample processing, if applicable 

 Select the air sample activity fraction, if applicable 

 Select rather to include I-131 intakes 

 Select the ICD cancer code 

 Select the distribution function

 Enter the case number 

 Select the location where the results will be saved 
ORAUT-OTIB-0054, Finding 9 (Workbook) 3 SC&A – April 2, 2015 

NOTICE: This document has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

After these items are entered, click on ADD. If you want to change any of these inputs, you must 

highlight the entire line, click REMOVE, and then start over. 

Once you are satisfied that the entries are correct, click on Get Results. 

Computations 

When the Get Results button is activated, the program goes through all the reactor types for the 

reactor group(s) selected (ATR1, ATR2, ATR3, FFTF1, FFTF2, N1, N2, TRIGA1, TRIGA2), up 

to nine total. It then provides the output in the form of three Excel spreadsheets. 

Output 

The results are provided in three Excel spreadsheets, labeled IREP, Summary, and Detail 1. A 

brief summary of these outputs is as follows: 

IREP – This spreadsheet lists the standard IREP table data and annual doses from the reactor 

that provides for the largest dose for the organ of concern. It also provides the type of reactor, 

(e.g., ATR2) that produced the largest dose. 

Summary – This spreadsheet provides a summary of the input parameters used, and the top 

reactor types that produced the largest doses for the organ of interest; along with the total dose 

derived for each of the these reactor types. 

Detail 1 – This spreadsheet provides the details for each radionuclide intake used in deriving the 

dose, along with a summary of the input parameters, the reactor type that produced the largest 

dose, solubility type, and annual doses. Note that the output results for the intake values are 

always converted to Bq/year, regardless of the units used in the input; this cannot be changed. 

SC&A’s Evaluation

There are an enormous number of combinations of reactor types, decay times, sample 

processing, radionuclide indicators, and applicable radionuclides to test in this Workbook and 

compare them to values in OTIB-0054 (i.e., Tables 7-1a-b, 7-2, 7-3a-i, 7-4a-b). Therefore, 

SC&A found that an efficient way to evaluate the Workbook was to run Workbook for the three 

examples on pages 68-71 of OTIB-0054 and compare the details of the results from the 

Workbook to those hand calculated and/or listed in OTIB-0054. In April 2014 SC&A verified 

that Workbook 1.2.0 performed correctly for Examples #1 and #2 using urine bioassay data; 

however, it did not perform correctly for Example #3 using air data. NIOSH was informed of 

this problem and recently released Workbook 1.5.11 that was to correct the air data problem. 

SC&A evaluated all three example using the new version of the workbook to insure that nothing 

had been altered that would impact the results when using urine bioassay data, and to verify that 

the problem was correct when using air data. This evaluation is summarized in the following 

examples. 

Example #1 –Urine Bioassay 

This example involves an intake period of 1960-1971 using gross beta urinalysis for a waste 

management worker; therefore, according to Table 5-3, page 12, a 1-year decay would be used. 
ORAUT-OTIB-0054, Finding 9 (Workbook) 4 SC&A – April 2, 2015 

NOTICE: This document has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

The bioassay urinalysis gross beta results listed in Table H-1, page 68, were used to derive a 

chronic intake of 161.36 pCi/d using the IMBA program (this corresponds to 76.0 pCi/d for 

ATR-1 as illustrated on page 68, but the Workbook requires a gross beta input, which is 161.36 

pCi/d, not the Sr-90 intake value of 76.0 pCi/d). Major processing of the bioassay samples was 

indicated; therefore, this would be selected during the input phase (corresponding to using Table 

7-2, page 19, of OTIB-0054). 

Entering these parameters into the Workbook provided the results in three spreadsheets as 

previously described. The outputs of these spreadsheets were evaluated and compared to the 

results listed in OTIB-0054. SC&A compared the output from the Detail 1 spreadsheet to the 

values in Table H-2, page 69 of OTIB-0054, and found them to match within rounding errors. 

Example #2 – Urine Bioassay 

This example involves an intake period of 1960-1971 using gross beta urinalysis for a spent fuel 

storage worker; therefore, according to Table 5-3, page 12, a 10-day decay would be used. The 

bioassay urinalysis gross beta results listed in Table H-3, page 70, were used to derive a chronic 

intake of 164.0 pCi/d using the IMBA program (this corresponds to 164.0 pCi/d x 2.14E-2 = 

3.51 pCi/d for ATR-1 as illustrated on page 70, but the Workbook requires a gross beta input, not 

the Sr-90 intake value). Minor processing of the bioassay samples was indicated; therefore, this 

would be selected during the input phase (corresponding to using Table 7-1a, page 18, of OTIB0054). 

Entering these parameters into the Workbook provided the results in three spreadsheets as 

previously described. Since the Workbook provides the details of the intakes for the reactor (in 

this case ATR-2) that produces the largest dose to the organ of interest, these intakes were 

adjusted to those for ATR-1 for comparison to the values in Table H-4 (which is an illustration 

of the intake values for ATR-1). SC&A converted the ATR-2 intake value results from the 

Workbook to ATR-1 intake values by multiplying the intake values for ATR-2 by the ATR-1 

activity fraction from Table 7-3a, then dividing by the ATR-2 activity fraction from Table 7-3b 

and then multiplying this result by the ATR-1 Sr-90 activity ratio from Table 7-1a, divided by 

the ATR-2 Sr-90 activity ratio from Table 7-1a. For example, for Co-60 the conversion from 

ATR-2 to ATR-1 intake value would be: 

Co-60 (pCi/d) = 5.693E-3 Bq/y x 27 pCi/Bq x (1/365 d/y) x 2.05E-4/2.07E-4 x 0.0214/0.0124 = 7.20 E-4 pCi/d

After these adjustments, SC&A compared the intake values in the output of the Workbook to the 

values in Table H-4, p. 70, of OTIB-0054, and found the values to match within rounding errors. 

Example #3 – Air Data 

This example involves an intake period of 1960-1971 using gross gamma air sample data for a 

worker in a spent fuel dissolution area; therefore, according to Table 5-3, page 12 a 180-day 

decay would be used. The maximum gross air concentration measured during the period 1960-

1971 was 1E-10 uCi/ml; this corresponds to 658 pCi/d gross gamma intake, and will be used to 

bound the intakes. 

SC&A found that the Workbook has a box that lists “Inhalation,” but the user cannot change this 

selection; i.e., the user cannot select inhalation or ingestion. However, when using air data, the 
ORAUT-OTIB-0054, Finding 9 (Workbook) 5 SC&A – April 2, 2015 

NOTICE: This document has been reviewed for Privacy Act information and has been cleared for distribution. 

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82. 

program automatically calculates both Inhalation and Ingestion intakes and provides the results 

in the output. Comparison of SC&A’s derived intake values using Workbook 1.5.11 to those 

listed in OTIB-0054 is provided for inhalation in Table 1, and for ingestion in Table 2. 

SC&A verified the ingested intake values for Example #3 using TIB-009 (OCAS-TIB-009

2004), page 4, i.e.: 

Ingested intake (pCi/d) = Inhaled intake (pCi/d) x 0.2 x 250 d x 1/2400m3

 Ingested intake (pCi/d) = Inhaled intake (pCi/d) x 0.0208 

Because of the recent revision in Table H-5 of OTIB-54, SC&A compared all the derived 

ingested values using TIB-009 (OCAS-TIB-009 2004) to those listed in Table H-5, and found 

them to match correctly. 

Table 1. Comparison of Workbook Inhalation Results to OTIB-0054 for Example #3 

ATR-1

Cs-137 

indictor

Workbook

Bq/year

180 day 

decay

Workbook

pCi/d

Table H-5

pCi/d

Intake from gross gamma air data

Input = 658 pCi/d

Workbook/

Table H-5

Ce-141 3.744E+02 2.77E+01 2.77E+01 1.00

Ce-144 3.109E+03 2.30E+02 2.30E+02 1.00

Co-60 3.142E-02 2.33E-03 2.32E-03 1.00

Cs-134 1.042E+02 7.71E+00 7.70E+00 1.00

Cs-137 1.628E+02 1.21E+01 1.20E+01 1.00

Eu-154 3.695E+00 2.74E-01 2.73E-01 1.00

I-131 8.513E-02 6.30E-03 6.29E-03 1.00

Nb-95 4.281E+03 3.17E+02 3.16E+02 1.00

Pm-147 4.411E+02 3.27E+01 3.26E+01 1.00

Pr-143 2.100E+00 1.55E-01 1.55E-01 1.00

Ru-103 3.646E+02 2.70E+01 2.70E+01 1.00

Ru-106 2.067E+02 1.53E+01 1.53E+01 1.00

Sr-89 1.065E+03 7.88E+01 7.87E+01 1.00

Sr-90 1.610E+02 1.19E+01 1.19E+01 1.00

Y-90 1.612E+02 1.19E+01 1.19E+01 1.00

Y-91 1.742E+03 1.29E+02 1.29E+02 1.00

Zr-95 2.246E+03 1.66E+02 1.66E+02 1.00

Total: 1068.2 1066.2
ORAUT-OTIB-0054, Finding 9 (Workbook) 6 SC&A – April 2, 2015

NOTICE: This document has been reviewed for Privacy Act information and has been cleared for distribution.

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82.

Table 2. Comparison of Workbook Ingestion Results to OTIB-0054 for Example #3

ATR-1

Cs-137 

indictor

Workbook

Bq/year

180 day 

decay

Workbook

pCi/d

Table H-5

pCi/d

Intake from gross gamma air data

Input = 658 pCi/d

Workbook/

Table H-5

Ce-141 7.787E+00 5.77E-01 5.77E-01 1.00

Ce-144 6.467E+01 4.79E+00 4.79E+00 1.00

Co-60 6.535E-04 4.84E-05 4.84E-05 1.00

Cs-134 2.167E+00 1.60E-01 1.60E-01 1.00

Cs-137 3.386E+00 2.51E-01 2.51E-01 1.00

Eu-154 7.686E-02 5.69E-03 5.69E-03 1.00

I-131 1.771E-03 1.31E-04 1.31E-04 1.00

Nb-95 8.905E+01 6.59E+00 6.59E+00 1.00

Pm-147 9.176E+00 6.79E-01 6.79E-01 1.00

Pr-143 4.368E-02 3.23E-03 3.23E-03 1.00

Ru-103 7.584E+00 5.62E-01 5.62E-01 1.00

Ru-106 4.300E+00 3.18E-01 3.18E-01 1.00

Sr-89 2.214E+01 1.64E+00 1.64E+00 1.00

Sr-90 3.349E+00 2.48E-01 2.48E-01 1.00

Y-90 3.352E+00 2.48E-01 2.48E-01 1.00

Y-91 3.623E+01 2.68E+00 2.68E+00 1.00

Zr-95 4.672E+01 3.46E+00 3.46E+00 1.00

 Total: 22.22 22.22

Conclusions

From the tests that SC&A performed, OTIB-0054 Workbook 1.5.11 correctly derives the intake 

values when using Sr-90 or Cs-137 as the indicating radionuclide when used in conjunction with 

the Apply Urine Activity Fraction or the Apply Air Sample Activity Fraction. Additionally, 

SC&A verified the revised ingestion values in Table H-5 were correct. SC&A had no findings in 

this workbook.
ORAUT-OTIB-0054, Finding 9 (Workbook) 7 SC&A – April 2, 2015

NOTICE: This document has been reviewed for Privacy Act information and has been cleared for distribution.

However, this report is pre-decisional and has not been reviewed by the Advisory Board on Radiation and Worker 

Health for factual accuracy or applicability within the requirements of 42 CFR 82.

References

OCAS-TIB-009. 2004. Technical Information Bulletin: Estimation of Ingested Intakes, Rev. 0,

National Institute for Occupational Safety and Health, Office of Compensation Analysis and 

Support, Cincinnati, Ohio. April 13, 2004.

ORAUT-OTIB-0054. 2007a. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Rev. 00, Oak Ridge Associated Universities, 

Cincinnati, Ohio. May 11, 2007.

ORAUT-OTIB-0054. 2007b. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses – Workbook 1.01, Oak Ridge Associated 

Universities, Cincinnati, Ohio. October 9, 2007.

ORAUT-OTIB-0054. 2007c. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Rev. 00 PC-1, Oak Ridge Associated 

Universities, Cincinnati, Ohio. November 19, 2007.

ORAUT-OTIB-0054. 2013a. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Rev. 01, Oak Ridge Associated Universities, 

Cincinnati, Ohio. June 13, 2013.

ORAUT-OTIB-0054. 2013b. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses – Workbook 1.2.0, Oak Ridge Associated 

Universities, Cincinnati, Ohio. November 21, 2013.

ORAUT-OTIB-0054. 2014. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Rev. 02, Oak Ridge Associated Universities, 

Cincinnati, Ohio. March 6, 2014.

ORAUT-OTIB-0054. 2015a. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses, Rev. 03, Oak Ridge Associated Universities, 

Cincinnati, Ohio. February 6, 2015.

ORAUT-OTIB-0054. 2015b. Fission and Activation Product Assignment for Internal DoseRelated Gross Beta and Gross Gamma Analyses – Workbook 1.5.11, Oak Ridge Associated 

Universities, Cincinnati, Ohio. March 2015.

SC&A. 2014. SC&A Review of NIOSH Responses to SC&A Comments on ORAUT-OTIB0054, Rev. 1: Fission and Activation Product Assignment for Internal Dose-Related Gross Beta 

and Gross Gamma Analyses. SC&A, Inc., McLean, VA and Saliant, Inc., Jefferson, MD. April 

2014.